ITER: Status of the Project - Fusion for Energy...Tests show rupture stress of ~1,400 MPa, well...

ITER: Status of the Project

M. Gasparotto

F4E - ITER Department

Barcelona - Spain

Information Day on H&CD Power Supplies for ITER

Barcelona, 27 th of May 2009

Information Day on H&CD Power Supplies for ITER - 27 May 09 2

What is fusion ?• When nuclei of light atoms collide at very high energy they fuse and

release an amount of energy much higher than the spent one

• Deuterium (D) + Tritium (T) is the “easiest” fusion reaction

• Fuels are largely available:

Deuterium is extracted from water

Tritium is produced inside the reactor

from Lithium (abundant on earth’s crust

and in the sea)


How does fusion work?

• In the core of the sun the

temperature is about 10 million

degrees.

• In fusion machines the

temperature is above 100 million

degrees to maximize the reaction

rate.

• A way to confine the plasma is to

use strong magnetic fields that

create a “cage” preventing the

particles to touch the walls of the

“container”.

• To avoid the losses at the end of

the “container” a closed, toroidal

configuration is used


What are the merits of fusion?

• Fusion will be a large source of energy with basic fuels largely

available in the sea

• No greenhouse gas emissions. Very low impact on the environment

• A fusion power station would not require the transport of radioactive

materials

• Power Stations would be inherently safe. No

possibility of “meltdown” or “runaway reactions”.

Fusion reactors work like a gas burner: once the

fuel supply is closed, the reaction stops

• No long-lasting radioactive waste to create a burden

on future generations

• With about 3000 m3 of water (->D) and 10 tons of Li

ore (->T), a future 1 GWel fusion power plant will be

able to operate one year


From JET …


… to ITER

16

17

18

19

20

21

22

0.1 1.0 10.0 100.0

T3

T3

W7-A

Pulsator

T10

ASDEX

ISAR 1

W7-AS

ASDEX

ASDEX U

JT-60UTore Supra

LHD

JET

DIII-DTFTR

Alcator C-

ModAlcator

TFTR

JT-60UJT-60U

Tokamak

DT exp. in tokamak

Stellarator

ITER

Log10N·T·τ

[m-3keV s]

Ti

[keV]

Burning plasmas

TFR

TEXT

OR

PLT

Break-

even


Who participates in ITER?

Involvement of parties representing over half of world’s population. The world’s largest Research project


Aims of ITER

• Demonstrate steady state fusion power production

• Produce about 500 MW of fusion power

• Power Amplification (Ratio Total Fusion Power/Input

Power to the Plasma) ≥≥≥≥10

• Demonstrate the technologies required for fusion

power stations (except structural materials inside

the vacuum vessel containing the plasma and the

breeding blanket)


ITER Parameters

Plasma Current (MA) 15

Toroidal Magnetic Field on Axis (T) 5.3

Machine Height (m) 26

Machine Diameter (m) 29

Plasma Volume (m3) 837

Operation Phase: about 20 years


ITER Updated Schedule


EU Main Components for ITER

Toroidal

Field Coil

Nb3Sn, 18 coils

Poloidal

Field Coils

NbTi

6 coils

Blanket

Module

421

modules

Vacuum Vessel

9 sectors

Additional

Heating

IC, EC, NBI

Inner Divertor

54 cassettes

Person


Construction Cost Sharing

Some procurement packages will be shared among several

Parties:


Magnets: Procurement

Magnets Toroidal Field Magnet

windings

100% 85.2

Toroidal Field Magnet

Structure: 12 fiberglass

rings

10% 5.14

Poloidal Field Magnet 1 & 6 50% 6.8

Poloidal Field Magnet 2 to 5 100% 33.6

Toroidal Field Magnet

Conductors

20% 43

Poloidal Field Magnet

Conductors

13% 9.653

kIUA*

*1kIUA = approx. 1.5 MEUR (2009 value)

EU Share


Magnets: Achievements

R&D on sub-scale pre-compression ring

successfully completed.

Tests show rupture stress of ~1,400 MPa, well above the limit required by ITER

The Poloidal Field Coil Insert

successfully tested in Naka (J).

Stable operation of the test coil

up to 52 kA at 6.4 T and 4.5 K.

Height 4 m

Width 3 m

Bmax=7.8 T

TOROIDAL FIELD

MODEL COIL

Co

urt

es

y o

f J

AE

A

Co

urt

es

y o

f E

NE

A


Magnets: Next steps in

Work Programme 2009

Procurement strategy developed in order to reduce risks and costs:

manufacturing of prototypes for TF winding packs and radial plates

� World wide call for tender to manufacture 1 or 2 radial plates full

scale prototypes to demonstrate the manufacturing feasibility and

find the cheapest fabrication route.

The activity should be carried out in parallel with the JA Domestic

Agency;

� Winding full scale production in phases.

The first phase includes two years of R&D with the manufacture of a

full scale dummy double pancake.


Vacuum Vessel: Procurement

Vacuum

Vessel

Main Vessel including

Blanket Manifolds and

Hydraulic Connectors

80% 99.36

kIUA*

The ITER Vacuum Vessel Torus

consists of 9 Sectors, each of

240 ton, 13 metres high and 6

metres wide, made from 60 mm

thick Stainless Steel plates and

with a double-wall with an

additional 250 tons of bolted

neutron shielding plates.


EU Share


Vacuum Vessel: Achievements

Construction of a full-sized, 20 Tons VV Poloidal

Sector Prototype successfully completed within required VV tolerances (+/- 10 mm) and using conventional manufacturing methods. It should be noted that arc welding produces distortions that are difficult to keep under control.

A novel technique of fabricating some VV straight

parts using only e-beam welding has also been

demonstrated for a full-representative mock-up.

6.2 metre long

e-beam welds

successfully

completed

Double-Wall,

± 5 mm

VACUUM

VESSEL

SECTOR

Co

urt

es

y o

f A

ns

ald

o

Co

urt

es

y o

f D

CN

S


Vacuum Vessel:

Next steps in Work Programme 2009

Procurement of the 7 sectors is planned as soon as the VV design

will be defined. This Procurement will also include the engineering

and manufacturing design for all sectors and the following

development activities:

*EB welding system development;

*qualification of ultrasonic tests;

*weld distortion control analysis.


In-Vessel Components:

First Wall / Blanket - Procurement

Blanket System Blanket First Wall 30% 26.1

Blanket Shield 10% 5.8

kIUA*

The design is at a very early stage;

The new strategy foresees a first wall separated from the

shield module. This approach will allow dismantling of these 2 parts

inside the vacuum vessel instead of in the hot cell.

EU Share




First Wall / Blanket:


High heat flux and thermal fatigue testing of FW mock-ups;

Be/CuCrZr joining development;

CuCrZr power-solid HIP development;

Irradiation and testing of blanket material (powder HIPed SS) and joints;



Divertor - Procurement

Divertor Cassette Integration 100% 11.2

Inner Target 100% 20.2

kIUA*EU Share


DIVERTOR CASSETTE AND PFCs20 MW/m2



Divertor:


Procurement of the CFC material for the prototype;

Preparation of Mock-ups in CFC and W;

Qualification of repair technologies;

Courtesy Ansaldo Courtesy Plansee


Remote Handling (RH)

Procurement

Remote Handling Divertor RH Equipment 100% 12

Transfer Cask System 50% 8.2

Viewing/Metrology

System

100% 6.8

Neutral Beam RH

Equipment

100% 6

kIUA*EU Share


Divertor cask


Remote Handling (RH):


Basic activities:

• Engineering support activities for studies in general areas;

• Qualification of radiation hard components (motors, sensors, etc).

•Specific activities:

• Neutral Beam RH: design activities in view of the Procurement

Arrangement signature;

• Study on Transfer Cask path in the ITER buildings;

• In-Vessel Viewing System (IVVS): detailed design;

Co

urt

es

y o

f T

els

tar


Diagnostics Magnetics 25% 0.825

Neutron Systems 25% 2.525

Optical Systems 25% 6.425

Bolometry 25% 1.675

Spectroscopic 25% 5.625

Microwave 25% 4.425

Operational

Systems

25% 2.75

Standard

Diagnostics

25% 10.125

kIUA*

F4E is responsible for the procurement of 9 diagnostic-related systems

for ITER (and enabling of a further 3).

Diagnostics - Procurement

EU Share



Activities launched in the diagnostic area during this Work Programme

will focus on completion of the designs for the diagnostics and

associated port plugs in the 9 diagnostic procurement packages for

which the EU is responsible, to the level appropriate for a conceptual

design review.

The activities will include:

�Design and engineering studies of each diagnostic system;

�System-level optimisation;

�Prototyping and testing of relevant components;

�Assessment of the technical specifications.

Diagnostics



Ion Cycloton H&CD Antenna (ICH),

Electron Cyclotron Upper Launcher (EC-UL),

Electron Cyclotron Power Sources (EC-PC):

Procurement

Electron

Cyclotron

Heating &

Current Drive

Upper Launcher 88% 7.832

RF Power

Sources

31% 10.075

Power Supplies 92% 12.788

kIUA*

Ion Cyclotron

Heating &

Current Drive

IC Antenna 88% 3.96

EU Share



Neutral Beam System (NBS)

Procurement

Neutral

Beam

Heating &

Current

Drive

Assembly & Testing 100% 3.8

Beam Source and

High Voltage Bushing

41% 4.75

Beamline

Components

100% 1.95

Pressure Vessel,

Magnetic Shielding

76% 5.95

Active Correction and

Compensation Coils

100% 6.1

Power Supply for

Heating Neutral Beam

31% 23.75

kIUA*EU Share



Neutral Beam System (NBS)


ELISE experiment preparation;

Design of the “NB components outside the scope of the NB Test

Facility”, (beam line and beam source vessels, passive magnetic

shield, drift duct, active correction and compensation coils and fast

shutter);

The detailed design and technical specifications of the components

and infrastructure of the NBTF;

Procurement of hardware for the Ion Source Test Facility first phase;

Procurement of infra-structure for the NBTF first phase;


Test Blanket Modules (TBM)

Activities

ITER Test Blanket Module (TBM) programme is a key step in the

blanket development to test prototypes in a tokamak environment and

validate the design codes. EU is developing HCLL (He-cooled Lithium-

Lead) and HCPB (He-cooled pebble bed) concepts adopting as

structural material the DEMO-relevant “9CrWVTa” reduced activation

ferritic martensitic steel EUROFER.


Fuel Cycle and Cryoplant

Procurement

kIUA*

Tritium Plant

Cryoplant

Hydrogen Isotopes

Separation

88% 5.456

Water Detritiation 88% 12.76

Cryoplant 50% 31.5

Vacuum

Pumping

Cryopumps 88% 9.856

Leak detection 88% 4.4

EU Share



Fuel Cycle and Cryoplant


Cryopumps:Completion of final design for the Prototype Torus Cryopump (PTC),

upgrading of TIMO-2 facility and testing of PTC in TIMO-2 to qualify

design ;

Manufacture of the PTC and Follow-up contract

Leak Detection:Performance studies and conceptual design for leak detection

system including proof-of-principle tests. Review of leak localization

concepts and their possible realization

Cryoplant:Optimisation of the design and specific analyses

Tritium Plant:Finalisation studies of Isotope Separation System and Water

Detritiation System


Buildings - Procurement

Buildings Concrete Buildings 100% 323.5

Steel Frame Buildings 100% 68.8

kIUA*EU Share


ITER Buildings form an integrated complex extending over an area of

about 50 hectares, including 28 buildings.

Reinforced concrete buildings

and selected infrastructure:

250.000 m³ of concrete,

building volume 750.000 m³,

foot print 21.000 m²;

Steel frame buildings:

foot print 29.000 m².

Information Day on H&CD Power Supplies for ITER - 27 May 09

Site Leveling: completed

Buildings - Achievements


Buildings


General Support-To-The-Owner Contract for the procurement of ITER

buildings (follow-up of the call for tender, monitor the main contracts etc);

Architect/Engineer for the procurement of ITER buildings (detailed

studies based on the preliminary technical specifications, prepare

technical specifications for construction contracts);

General Health and Safety Coordination Protection for ITER buildings

(prepare detailed rules, follow up the implementation).


• Tokamak Complex Seismic Isolators Fabrication;

• PF Coil Fabrication Building Design-and-Build

• Excavation and drainage of the Tokamak Complex Foundations

Main construction contracts:

Buildings



THANK YOU FOR

YOUR ATTENTION

Date post:	24-Sep-2020
Category:	Documents
Upload:	others
View:	1 times
Download:	0 times

ITER: Status of the Project - Fusion for Energy...Tests show rupture stress of ~1,400 MPa, well...

Documents